Results 1 to 10 of about 1,936 (209)

IMPGYRO: The full-orbit impurity transport code for SOL/divertor and its successful application to tungsten impurities

Computer Physics Communications, 2020
Abstract In future fusion reactors, tungsten (W) is currently regarded as one of the most feasible candidates for the plasma-facing components (PFCs). Once the W impurities sputtered from the PFCs penetrate into the core plasma, the large radiation cooling and fuel dilution, which leads to the deterioration of the core plasma performance, take place.
Shohei Yamoto, Y Homma, K Hoshino
exaly   +12 more sources

The influence of E× B drift on tungsten target erosion and W impurity transport during neon seeding on EAST

Nuclear Fusion, 2023
Mitigating tungsten (W) wall erosion and core accumulation are vitally important for the steady-state operation of tokamaks. It is well known that drifts have a great impact on the transport of charged particles in the edge region, which could affect W ...
Yilin Wang, Chaofeng Sang, Xuele Zhao, Yihan Wu, Qingrui Zhou, Yanjie Zhang, Dezhen Wang   +6 more
doaj   +4 more sources

Tungsten core accumulation study in EAST plasma with lower tungsten divertor by kinetic impurity transport model

Nuclear Materials and Energy, 2022
Tungsten (W) impurity transport and the corresponding core W accumulation is a critical issue in tokamak with W as plasma facing material. In this work, a kinetic W impurity transport code based on the guiding center approximation is applied for the ...
Yihan Wu, Qingrui Zhou, Chaofeng Sang, Yanjie Zhang, Yilin Wang, Dezhen Wang   +5 more
doaj   +4 more sources

Impurity transport simulation in the peripheral plasma in the large helical device with tungsten closed helical divertor

Nuclear Materials and Energy, 2018
Long pulse plasma discharges in the Large Helical Device have been often interrupted by iron dust emission induced by electric arcing on the surface of the vacuum vessel.
M. Shoji, G. Kawamura, S. Masuzaki, T. Morisaki   +3 more
doaj   +3 more sources

The transport of tungsten impurities induced by the intrinsic carbon during upper-single null discharge on EAST tokamak

Nuclear Materials and Energy, 2020
The transport as well as accumulation of tungsten (W) impurity is one of the critical issues for the W divertor operation. The EAST tokamak with W and graphite divertor targets, provides a good platform for the investigation of W impurity behaviors.
Qingrui Zhou, Chaofeng Sang, Guoliang Xu, Rui Ding, Xuele Zhao, Yilin Wang, Dezhen Wang   +6 more
doaj   +4 more sources

Simulation study of the influence of E× B drift on tungsten impurity transport in the scrape-off layer

Nuclear Fusion, 2023
Tungsten (W) is used as the plasma-facing material in the divertor region of future fusion reactors, such as ITER; however, its concentration in the core plasma must be maintained at an extremely low level.
Jin Guo, Yuchen Xu, Shifeng Mao, Minyou Ye   +3 more
doaj   +3 more sources

Preliminary Result of Neoclassical Impurity Transport Affected by ICRH with a 4-D Fokker-Planck Code [PDF]

EPJ Web of Conferences
To understand the role of ion cyclotron resonance heating (ICRH) in mitigating tungsten accumulation, we evaluate the impact of ICRH-induced poloidal asymmetries on neoclassical impurity transport using a newly developed 4-D Fokker–Planck code (FP4D ...
Jeong Yunho, Lee Hyeonjun, Bertelli Nicola, Yoon Eisung, Lee Jungpyo   +4 more
doaj   +2 more sources

Interpretative modeling of impurity transport and tungsten sources in WEST boundary plasma [PDF]

Nuclear Fusion, 2021
The contamination of core plasma by high-Z impurities, especially tungsten (W), is the main reason of very high level of radiated power in WEST experiments. Intrinsic light impurities, mainly oxygen and carbon, play a dominant role in the sputtering of W on plasma facing components.
G. Ciraolo, S. Di Genova, H. Yang, A. Gallo, N. Fedorczak, H. Bufferand, J.P. Gunn, P. Tamain, R. Guirlet, C. Guillemaut, C. Desgranges, C. Bourdelle, E. Tsitrone, J. Bucalossi, M. Scotto D’Abusco, E. Serre, Y. Marandet, M. Raghunathan, A. Sepetys, J. Romazanov, A. Kirschner, S. Brezinsek, the WEST Team   +22 more
core   +6 more sources

Global modelling of tungsten impurity transport based on the drift-kinetic equation

Nuclear Fusion, 2019
A global kinetic simulation model of collisional impurity transport is developed for evaluating the radial particle flux of tungsten impurity in the edge region of a tokamak plasma. Here, the plasma including the impurity and the background ion is presupposed to be quasi-steady.
Ryutaro Kanno, Gakushi Kawamura, Masanori Nunami, Yuki Homma, Akiyoshi Hatayama, Kazuo Hoshino   +5 more
openaire   +3 more sources

Impurity transport and halo current effects on tungsten divertor system

Journal of Radiation Research and Applied Sciences, 2020
This paper presents the development of theoretical model for the purpose to calculate and analyze halo and eddy current effects in the tungsten divertor of Tokamak (Fusion) reactor.
Shahab Ud-Din Khan, Riaz Khan
exaly   +2 more sources